• 대한한방내과학회지
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• 제25권4호
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• pp.274-288
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• 2004

Objectives : This study was designed to evaluate the effect on cytotoxicity of Bojungikki-tang(BIT) in human lung cancer H460 cells. Methods : BIT-induced cell death was confirmed as apoptosis characterized by chromatin condensation and increase of the $sub-G_1$, DNA content. It was tested whether the water extract of BIT affects the cell cycle regulators such as, p2l/Cipl, p27/Kipl, cyclin $B_1$. Results : The data showed that treatment of BIT decreased the viability of H460 cells in a dose-dependent manner. p2l/Cip1 is gradually decreased by the addition of the cells with BIT extract. Interestingly, p27/Kip1 is not detected for 24 hr after the addition of BIT extract, however, after 24 hr, p27/Kipl markedly increased. In addition, cyclin $B_1$, decreased in a time dependent manner after the addition of the water extract. The activation of caspase -3 protease was further confirmed by degradation of procaspase-8 protease andpoly(ADP-ribose) polymerase(P ARP) by BIT in H460 cells. Moreover, BIT induced the increase of Bak expression. Conclusion : These results suggest that the extract of BIT exerts anticancer effects to induce the death of human lung cancer H460 cells via down regulation of cell cycle regulators such as p2l/Cip1, and cyclin B1 or up regulation of cell cycle regulators such as p27/Kip1. Moerover results suggest that BIT induces an apoptosis in H460 cells via activation of intrinsic caspase cascades.

• 한국산업보건학회지
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• 제16권2호
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• pp.145-151
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• 2006

Because of the limitations of maximal load tests for $VO_2max$, submaximal tests using cycle ergometer are used for field study in general. This study was conducted to evaluate validity of various submaximal tests using cycle ergometer. This study had been conducted during May to June 2005, which subjects were 15 males and 15 females in twenties. Experiment was performed with restrictive conditions which regulated ambient temperature, noise, and entrance restriction. Submaximal load test protocols including YMCA Protocol (YP), ${\AA}strand$-Rhyming Protocol (ARP), Relative heart ratio Protocol (RP), and Ramp test Protocol (RP) were compared with maximal load test which used gas mask analyser using Bruce Protocol. All submaximal load tests were highly related with maximal load test (Spearman's correlation coefficient > 0.60) with statistical significancy. The highest correlation coefficient with maximal test was found in RP. Three submaximal test results except RP were significantly different with maximal test results (Wilcoxon rank test). All submaximal tests had high validity. The reason why RP had highest validity might be that it represents Korean physical strength and individual differences better than the others. RP using cycle ergometer would make easy to study for physical capacity evaluation and field workload estimation.

• 한국정보과학회논문지:소프트웨어및응용
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• 제32권12호
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• pp.1178-1191
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• 2005

본 논문은 NuSCR 정형 명세 언어로 작성된 소프트웨어 요구 명세로부터 소프트웨어 고장 수목을 생성하는 방법에 대하여 제안하였다 본 연구에서 제안하는 소프트웨어 고장 수목은 소프트웨어의 구조와 동작에 대한 요구 사항을 반영하는 통합된 형태의 고장 수목으로, 안전성에 대한 복합적인 분석이 가능하다. 이러한 소프트웨어 고장 수목을 생성하기 위하여 NuSCR 정형 명세언어의 구성 요소 각각에 대한 템플릿을 정의하고, 이들 템플릿을 사용하여 소프트웨어 고장 수목을 생성하는 방법을 제안하였다. 그리고, 제안된 방법의 유용성을 평가하기 위해 현재 국내 원전계측제어시스템 개발사업단에서 개발 중인 차세대 원자력 시스템 APR1400에 사용될 원자로 보호 시스템의 핵심 트립 논리에 대하여 고장 수목을 생성하고 분석 하였다.

• Journal of Radiation Protection and Research
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• 제39권4호
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• pp.176-181
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• 2014

The object of this paper is to evaluate the fission product inventories and radiological doses in a non-LOCA event, based on the U.S. NRC's regulatory methodologies recommended by the TID-14844 and the RG 1.195. For choosing a non-LOCA event, one fuel assembly was assumed to be melted by a channel blockage accident. The Hanul nuclear power reactor unit 6 and the CE $16{\times}16$ fuel assembly were selected as the computational models. The burnup cross section library for depletion calculations was produced using the TRITON module in the SCALE6.1 computer code system. Based on the recently licensed values for fuel enrichment and burnup, the source term calculation was performed using the ORIGEN-ARP module. The fission product inventories released into the environment were obtained with the assumptions of the TID-14844 and the RG 1.195. With two kinds of source terms, the radiological doses of public in normal environment reflecting realistic circumstances were evaluated by applying the average condition of meteorology, inhalation rate, and shielding factor. The statistical analysis was first carried out using consecutive three year-meteorological data measured at the Hanul site. The annual-averaged atmospheric dispersion factors were evaluated at the shortest representative distance of 1,000 m, where the residents are actually able to live from the reactor core, according to the methodology recommended by the RG 1.111. The Korean characteristic-inhalation rate and shielding factor of a building were considered for a series of dose calculations.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.378-383
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• 2016

Background: Radiation dose rates in PRIDE facility is evaluated quantitatively for assessing radiation safety of workers because of large amounts of depleted uranium being handled in PRIDE facility. Even if direct radiation from depleted uranium is very low and will not expose a worker to significant amounts of external radiation. Materials and Methods: ORIGEN-ARP code was used for calculating the neutron and gamma source term being generated from depleted uranium (DU), and the MCNP5 code was used for calculating the neutron and gamma fluxes and dose rates. Results and Discussion: The neutron and gamma fluxes and dose rates due to DU on spherical surface of 30 cm radius were calculated with the variation of DU mass and density. In this calculation, an imaginary case in which DU density is zero was added to check the self-shielding effect of DU. In this case, the DU sphere was modeled as a point. In case of DU mixed with molten salt of 50-250 g, the neutron and gamma fluxes were calculated respectively. It was found that the molten salt contents in DU had little effect on the neutron and the gamma fluxes. The neutron and the gamma fluxes, under the respective conditions of 1 and 5 kg mass of DU, and 5 and $19.1g{\cdot}cm^{-3}$ density of DU, were calculated with the molten salt (LiCl+KCl) of 50 g fixed, and compared with the source term. As the results, similar tendency was found in neutron and gamma fluxes with the variation of DU mass and density when compared with source spectra, except their magnitudes. Conclusion: In the case of the DU mass over 5 kg, the dose rate was shown to be higher than the environmental dose rate. From these results, it is concluded that if a worker would do an experiment with DU having over 5 kg of mass, the worker should be careful in order not to be exposed to the radiation.

• 천문학회지
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• 제36권3호
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• pp.167-175
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• 2003

There is accumulating evidence for a strong link between nuclear starbursts and AGN. Molecular gas in the central regions of galaxies plays a critical role in fueling nuclear starburst activity and feeding central AGN. The dense molecular ISM is accreted to the nuclear regions by stellar bars and galactic interactions. Here we describe recent observational results for the OB star forming regions in M51 and the nuclear star burst in Arp 220 - both of which have approximately the same rate of star formation per unit mass of ISM. We suggest that the maximum efficiency for forming young stars is an Eddington-like limit imposed by the radiation pressure of newly formed stars acting on the interstellar dust. This limit corresponds to approximately 500 $L_{\bigodot} / M_{\bigodot}$ for optically thick regions in which the radiation has been degraded to the NIR. Interestingly, we note that some of the same considerations can be important in AGN where the source of fuel is provided by stellar evolution mass-loss or ISM accretion. Most of the stellar mass-loss occurs from evolving red giant stars and whether their mass-loss can be accreted to a central AGN or not depends on the radiative opacity of the mass-loss material. The latter depends on whether the dust survives or is sublimated (due to radiative heating). This, in turn, is determined by the AGN luminosity and the distance of the mass-loss stars from the AGN. Several AGN phenomena such as the broad emission and absorption lines may arise in this stellar mass-loss material. The same radiation pressure limit to the accretion may arise if the AGN fuel is from the ISM since the ISM dust-to-gas ratio is the same as that of stellar mass-loss.

• 한국해안해양공학회지
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• 제6권3호
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• pp.205-215
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• 1994

난류모형을 도입하여 풍성류에 대한 3차원 수치모형을 수립하고, 풍성류 계산에 있어서 연직 와점성계수 산정방법들에 대한 비교평가를 수행하였다. 검토된 방법은 함수형(0-방정식), 1-방정식, 2개의 2-방정식 난류모형($ extsc{k}$-$\varepsilon$과 $textsc{k}$-ι)이며, 난류모형은 난류확산 특성길이의 연직분포에 대한 비교를 통하여 각 방법의 특징이 검토되었다. 양단이 막힌 수로와 순환수로에서 유속의 연직분포 계산결과를 수리실험자료와 비교검증하였다. 분석결과에 의하면 1-방정식 난류모형에 적합한 난류확산 특성길이 산정식은 포물선형이었으며, 2-방정식 난류모형($textsc{k}$-ι 모형과 $textsc{k}$-$\varepsilon$모형)은 대체로 실험치와 일치하는 경향을 보였다. 바람에 의한 영향이 전수심에 미치지 않는 경우에 가정된 연직 와점성계수의 분포는 바람이 영향을 미치는 수심까지만 적용되며, 영향이 없는 수심에서는 연직확산이 거의 일어나지 않아 적정성계수의 크기가 0에 가까웠다.

• Nuclear Engineering and Technology
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• 제37권1호
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• pp.91-100
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• 2005

Kyung-hee Thorium Fuel (KTF), a heterogeneous thorium-based seed and blanket design concept for pressurized light water reactors, is being studied as an alternative to enhance proliferation resistance and fuel cycle economics of PWRs. The proliferation resistance characteristics of the KTF assembly design were evaluated through parametric studies using neutronic performance indices such as Bare Critical Mass (BCM), Spontaneous Neutron Source rate (SNS), Thermal Generation rate (TG), and Radio-Toxicity. Also, Fissile Economic Index (FEI), a new index for gauging fuel cycle economy, was suggested and applied to optimize the KTF design. A core loaded with optimized KTF assemblies with a seed-to-blanket ratio of 1: 1 was tested at the Korea Next Generation Reactor (KNGR), ARP-1400. Core design characteristics for cycle length, power distribution, and power peaking were evaluated by HELIOS and MASTER code systems for nine reload cycles. The core calculation results show that the KTF assembly design has nearly the same neutronic performance as those of a conventional $UO_2$ fuel assembly. However, the power peaking factor is relatively higher than that of conventional PWRs as the maximum Fq is 2.69 at the M$9^{th}$ equilibrium cycle while the design limit is 2.58. In order to assess the economic potential of a heterogeneous thorium fuel core, the front-end fuel cycle costs as well as the spent fuel disposal costs were compared with those of a reference PWR fueled with $UO_2$. In the case of comprising back-end fuel cycle cost, the fuel cycle cost of APR-1400 with a KTF assembly is 4.99 mills/KWe-yr, which is lower than that (5.23 mills/KWe-yr) of a conventional PWR. Proliferation resistance potential, BCM, SNS, and TG of a heterogeneous thorium-fueled core are much higher than those of the $UO_2$ core. The once-through fuel cycle application of heterogeneous thorium fuel assemblies demonstrated good competitiveness relative to $UO_2$ in terms of economics.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2748-2754
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• 2022

Because existing reactant coolant system (RCS) leakage detection mechanisms are insensitive to small leaks, a real-time, direct detection system with a detection threshold below 0.5 gpm·hr^-1 was studied. A beta-ray detection system using a silicon detector with good energy resolution for beta rays and a low gamma-ray response was proposed. The detection performance in the leakage condition was evaluated through experiments and simulations. The concentration of ¹⁶N in the coolant corresponding to a coolant leakage of 0.5 gpm was calculated using the analytic method and ORIGEN-ARP. Based on the concentration of ¹⁶N and the measurement of the silicon detector with ⁹⁰Sr/⁹⁰Y, the beta-ray count rate was estimated using MCNPX. To evaluate the effect of gamma rays inside the containment building, the signal-to-noise ratio (SNR) was calculated. To evaluate the count rate ratio, the radiation field inside the containment building was simulated using MCNPX, and response evaluation experiments were performed using beta and gamma rays on the silicon detector. The expected beta-ray count rate at 0.5 gpm leakage was 7.26 × 10⁵ counts/sec, and the signal-to-background count rate ratio exceeded 88 for a transport time of 10 s, demonstrating its suitability for operation inside a reactor containment building.

• Journal of Positioning, Navigation, and Timing
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• 제12권1호
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• pp.83-89
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• 2023

The Korea Augmentation Satellite System (KASS) system is a Satellite Based Augmentation System (SBAS) under development to provide APV-I SBAS service in the Republic of Korea. The KASS ground segment generates correction and integrity information for GPS measurements of KASS users using the accurate positions of KASS Reference Station (KRS) antenna phase centers. For this reason, the accuracy of KRS reference points through geodetic survey campaigns is one of the important factors for providing the KASS service in compliance with the required navigation performance. In order to obtain accurate positions, two geodetic survey campaigns were performed at several reference points, such as Mark, Center of Mast at Ground Level (CMGL), and Center of Hole in Top Plate (CHTP), of each KRS site using three different survey methods, the Virtual Reference Station (VRS), Flächen Korrektur Parameter (FKP), and raw data post-processing methods. By comparing and analyzing the results, the computed coordinates of the reference points were verified and Antenna Phase Center (APC) positions were calculated using KRS Antenna Reference Point (ARP) data, and the first KASS Site Acceptance Test (SAT#1) was performed successfully using the verified APC coordinates. After the first site survey activities, the KASS operators should maintain the coordinates with the required performance such that the overall KASS navigation performance commitment is guaranteed during the lifetime of 15 years. Therefore, the maintenance plan for the KRS antenna coordinates should be developed before the commissioning of KASS operation planned after 2023. Therefore, this paper presents a geodetic survey method selected for the maintenance activities and provides the rationale for using this method.